Proceedings of the KSME Conference (대한기계학회:학술대회논문집)
- 2001.06a
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- Pages.782-787
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- 2001
Finite Element Limit Analysis of a Nuclear Reactor Lower Head Considering Thermal Softening in Severe Accident
중대사고에서의 열적 연화를 고려한 원자로 하부구조의 유한요소 극한해석
- Kim, Kee-Poong (KAIST) ;
- Huh, Hoon (KAIST) ;
- Park, Jae-Hong ;
- Lee, Jong-In
- Published : 2001.06.27
Abstract
This paper is concerned with the global rupture of a nuclear reactor pressure vessel(RPV) in a severe accident. During the severe reactor accident of molten core, the temperature and the pressure in the nuclear reactor rise to a certain level depending on the initial and subsequent condition of a severe accident. While the rise of the temperature cause the thermal softening of RPV material, the rise of the internal pressure could cause failure of the RPV lower head. The global rupture of an RPV is simulated by finite element limit analysis for the collapse pressure and mode and this analysis results have been compared with a variation of the internal pressure of RPV. The finite element limit method is a systematic tool to secure the safety criteria of a nuclear reactor and to evaluate the in-vessel corium retention.
Keywords